6results about How to "Reduce Radiation Risk" patented technology

The utility model discloses a nuclear power station water quality purifying and filtering integrated device which comprises an airtight container, a water inlet, a water outlet, a charging port and a discharging port, and the interior of the airtight container is divided into an upper-layer compartment, a middle-layer compartment and a lower-layer compartment from top to bottom through at least two partition plates. The upper-layer compartment, the middle-layer compartment and the lower-layer compartment are sequentially communicated through a plurality of water distributors arranged on the partition plate, and the middle-layer compartment is filled with ion exchange resin; the water inlet is communicated with the upper-layer compartment for water inflow, and the water outlet is communicated with the lower-layer compartment for water outflow; the charging hole is communicated with the upper part of the middle-layer compartment and is used for charging the ion exchange resin, and the discharging hole is communicated with the lower part of the middle-layer compartment and is used for discharging the ion exchange resin. The water quality purification and filtration integrated device for the nuclear power station is integrated equipment, occupies less space, is simple in pipeline, and can be used for remotely replacing the ion exchange resin and reducing the radiation risk.

The invention relates to a rotary table device convenient for long-distance disassembly and assembly, which comprises a rotary fixed base, a rotary support transition plate, a rotary support, a rotary large disc, a positioning pin, a C-shaped fixed clamp and an electric wrench, and the top of the rotary fixed base is provided with an upper boss and a positioning key slot which are in positioning fit with the rotary support transition plate; a positioning pin hole for positioning the slewing bearing transition plate is also formed in the slewing fixing base; the rotary fixed base is fixed on the ground through foundation bolts, and has the advantages of few fault points, stable operation, high intelligent degree and the like.

The present application relates to the technical field of medical isotope production, and particularly relates to a solid target disassembling device and method. The disassembling device comprises a pushing assembly, a first cutting assembly and a second cutting assembly. The pushing assembly comprises a horizontal moving module, a tray and a moving frame. The tray and the moving frame are both installed on the horizontal moving module. A groove is formed on the moving frame, and the tray is located on the lower side of the groove. The first cutting assembly comprises a support, a vertical moving module and a flywheel. The support is located on the upper side of the pushing assembly. A placing groove for installing the target is formed on the support. The vertical moving module is installed on the support and is perpendicular to the horizontal moving module. The flywheel is installed on the vertical moving module. The second cutting assembly comprises a driving mechanism and a cutting piece. The driving mechanism is located at the end of the horizontal moving module. The cutting piece is installed on the bottom side of the driving mechanism. The present application solves the problems of high safety risk, low efficiency, difficult disassembly and difficulty in ensuring the integrity of the target material in the prior art.

This invention discloses a membrane-borne self-driven storage and retrieval device for online monitoring of αβ radioactive aerosols, relating to the technical field of aerosol storage equipment. It includes a storage chamber and a combination tray mechanism. The storage chamber has retrieval and placement ports on its side wall. The combination tray mechanisms are stacked within the storage chamber, with adjacent combination tray mechanisms connected and fixed by support pillars. A rotating sleeve is installed on the bottom combination tray mechanism, driven by an externally mounted motor. This invention designs each layer of the combination tray mechanism as an integrated top and bottom tray structure, with storage ports one and two respectively. This allows a single layer to simultaneously and independently store new membrane boxes and recycled old membrane boxes, achieving "dual-purpose storage" and effectively doubling the effective storage capacity. Combined with the rotatable sleeve design, the multi-layer combination tray mechanism can be cyclically positioned, allowing the retrieval and placement ports to sequentially connect to the storage positions on each layer, further maximizing the utilization of vertical space.

This invention relates to the technical field of radioactive waste treatment, and discloses a combined packaging container for radioactive waste in a hot chamber, a shielding system, and a method for shielding radioactive waste. The combined packaging container for radioactive waste in a hot chamber includes a transfer container, a sealing container, and a fixing mechanism. The transfer container has a gripping part on its periphery for a robotic arm to grip and empty the container. The sealing container includes a sealing cap and a sealing body. The sealing cap is closably connected to the sealing body, and the sealing body defines a sealing cavity for storing radioactive waste. The sealing cap has a first clamping position for connection to the robotic arm, and the sealing body has a second clamping position. The fixing mechanism has a clamping part and a movable part connected to each other. The clamping part is driven by the movable part to switch between a first position and a second position. The combined packaging container for radioactive waste in a hot chamber of this invention can improve the sealing performance of the sealing container and reduce the radiation risk of radioactive waste.

This invention relates to the field of ridge filter design technology, and discloses a design method, system, device, and storage medium for ridge filters. The method includes acquiring first and second actual water depth dose distribution data for proton and heavy ion beams with multiple energies; performing Monte Carlo simulation on the proton and heavy ion beams to obtain a Monte Carlo beam model; constructing a geometric optimization model for the ridge filter using its geometric parameters as optimization variables, maximizing its performance index as the objective function, and using geometric parameter constraints as constraints; and solving the geometric optimization model using a particle swarm optimization algorithm to obtain the optimal geometric parameters. This invention can improve the parameter design accuracy of ridge filters, reduce the processing accuracy requirements of ridge filters, improve the flatness of the effective biological dose in the extended Bragg peak, and reduce the radiation risk from secondary neutrons.